Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

ZHANG Bin; CHEN Yi-Xue; WANG Wei-Jin; YANG Shou-Hai; WU Jun; YIN Wen; LIANG Tian-Jiao; JIA Xue-Jun

doi:10.1088/1674-1137/35/8/017

Chinese Physics C> 2011, Vol. 35> Issue(8) : 791-795 DOI: 10.1088/1674-1137/35/8/017

Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

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Abstract：
The construction of China Spallation Neutron Source (CSNS) has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.

References

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ZHANG Bin, CHEN Yi-Xue, WANG Wei-Jin, YANG Shou-Hai, WU Jun, YIN Wen, LIANG Tian-Jiao and JIA Xue-Jun. Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design[J]. Chinese Physics C, 2011, 35(8): 791-795. doi: 10.1088/1674-1137/35/8/017

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Received: 2010-10-08
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通讯作者: 陈斌, bchen63@163.com

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沈阳化工大学材料科学与工程学院沈阳 110142

Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

Received Date: 2010-10-08

Accepted Date: 1900-01-01

Available Online: 2011-08-05

Abstract: The construction of China Spallation Neutron Source (CSNS) has been initiated in Dongguan, Guangdong, China. Thus a detailed radiation transport analysis of the shutter neutron beam stop is of vital importance. The analyses are performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method. The target of calculations is to optimize the neutron beamline shielding design to guarantee personal safety and minimize cost. Successful elimination of the primary ray effects via the two-dimensional uncollided flux and the first collision source methodology is also illustrated. Two-dimensional dose distribution is calculated. The dose at the end of the neutron beam line is less than 2.5 μSv/h. The models have ensured that the doses received by the hall staff members are below the standard limit required.

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Preliminary shielding analysis in support of the CSNS target station shutter neutron beam stop design

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